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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Comanche Peak adds years to operating licenses
The Nuclear Regulatory Commission has renewed the operating licenses of Comanche Peak Units 1 and 2 for an additional 20 years.
Unit 1’s operating license now expires on February 8, 2050, and Unit 2’s on February 2, 2053.
L. Crosatti, D. L. Sadowski, S. I. Abdel-Khalik, M. Yoda, ARIES Team
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 96-100
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8883
Articles are hosted by Taylor and Francis Online.
Extensive experimental and numerical studies of the planar jet impingement concept used in gas-cooled T-tube divertor modules have been previously performed at Georgia Tech.1 The experiments were used to validate the numerical CFD model based on the FLUENT[registered] software package. However, the test module used in those experiments did not duplicate the exact geometry of the T-tube divertor, particularly the single-sided nature of the incident heat flux. In this paper, the thermal performance of a prototypical T-tube divertor module is experimentally and numerically examined. The test module has been designed and constructed to match the geometry, dimensions, material properties, and single-sided heating configuration of the actual T-tube divertor. Experiments were performed using air as the coolant with different values of the incident heat flux. The coolant flow rate and inlet pressure were selected to span the expected range of non-dimensional parameters for the actual helium-cooled T-tube divertor design. The experimental values of the local heat transfer coefficient and pressure drop show good agreement with the numerical (FLUENT[registered] 6.3) predictions. The data obtained in this investigation provide added confidence in the predicted performance of the T-tube divertor concept, and the ability of the FLUENT CFD software package to predict its thermal performance, as well as the thermal performance of other complex gas-cooled high heat flux components.